ML18005A857

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Forwards Info Re Implementation Status of Identified TMI Action Plan Items in Response to 890414 Request.Time Provided for Determining Status of Implementation of Items Extremely Short & Burdensome to Personnel
ML18005A857
Person / Time
Site: Harris 
Issue date: 04/18/1989
From: Eury L
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NLS-89-109, NUDOCS 8904240337
Download: ML18005A857 (18)
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Text

, A.CCKLKWTED Dl BUT10N DKMONSTRa o~ . SYSTEM WEGUL'ATORY FORMATION DISTRIBUTION SY M (RZDS)

I ACCESSION NBR:8904240337 DOC.DATE: 89/04/18 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION EURYFL.W. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards info re implementation status of identified TMI action plan items in response to 890414 request.

DISTRIBUTION CODE'003D OR/Licensing COFZES RECEIVED'LTR I ENCL Submittal: Suppl 1 to NUREG-0737(Generic L SIZE'ITLE:

Ltr 82-33 )

NOTES:Application for permit renewal filed. 05000400 8

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 7 7 BECKER,D 1 1 INTERNAL: NRR/DLPQ/HFB 10 1 1 NUDOCS-ABSTRACT 1 1 OC/LFMB 1 0 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NOXE 'IO ALL 'RIDS" RECIPII&IS:

PLEASE HELP US TO REDUCE %RBBEi CORI'ACT IHE DOCUMENI'XÃIPOL DESKF RXN Pl-37 (EXT. 20079) K) ElZMZHRH3 KXIR MNB PKN DXSTIMK7ZZGN ZZSTS KK DOCUtKHIS YOU DONFT NEZDf TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 16

0 SMP Carolina Power & Light Company SERIAL: NLS-89>>109 APRl 8 889 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Nashington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 IMPLEMENTATION STATUS OF TMI ACTION PLAN ITEMS Gentlemen:

The information attached responds to your request of April 14, 1989 regarding the status of the identified TMI Action Plan Items. Please note that the time provided to determine the status of implementation of all TMI items as required by your request has been extremely short and that significant personnel burden has been involved. Moreover, the attached notations regarding status of individual items are necessarily brief and cannot address all of the details of the more complex issues. Taking these constraints into account, I certify that to the best of my knowledge the attached information is correct.

Please refer any questions regarding this submittal to Mr. M. R. Oates at (919) 546-6063.

Yours very truly, L. W. EU Executive Vice President Power Supply LME/JHE/crs (306CRS)

Attachments cc: Mr. R. A. Becker Mr. M. H. Bradford Mr. S. D. Ebneter aqo4240337 8'P4gio400 DOCg 05000NU oo>

411 Fayettevilte Street o P. O. Box 1551 e Raleigh, N. C.

27602

I NOTES TO TMI ITEM STATUS TABLE Note has fully implemented the requirements for an SPDS with the 1'HNPP exception that one Human Engineering Discrepancy (HED No. 31G1-6019) remains outstanding. A modification to correct this HED is currently in progress and scheduled to be completed by May 19, 1989.

Note 2 SHNPP has completed all required actions for this item, however the NRC has not yet issued a final Safety Evaluation Report (SER). If additional requirements are identified in the final SER, CP&L will address them at that time.

GUIDELINES FOR UPDATING TMI STATUS

1. The enclosure provides a complete listing of all TMI requirements from NUREG-0737 and NUREG-0737 Supplement 1. Regulatory Guide 1.97 requirements, although addressed in Supplement 1 to NUREG-0737, are excluded since they did not originate from the TMI Action Plan. This listing consists of a matrix of items applicable to both operating reactors and operating license applicants (NTOLS) as of November, 1980, as shown in NUREG-0737 Enclosure 1 and 2, respectively. All items which are not listed identically fn Enclosure 1 and 2 are marked with asterisks to indicate differences between operating reactor and NTOL requirements.

Whenever these differences occur, enter data in accordance with the appropriate title, regardless of the TMI Action Plan item number listed.

Your NRG Project Manager has indicated which issues are shown as unimplemented in the NRC tracking system. Please review the entire listing for each licensed reactor unit. Where an item was not applicable for your facility, mark N/A in the implementation status column.

2. Where an item was applicable to your facility but no changes were necessary, mark NC in the implementation status column.
3. Where an item was applicable to your facility and changes are complete mark G in: the implementation status column. If the date is readily available (month and year) we request you provide it, however, C is sufficient.
4. Where an item was applicable to your facility and fs not fully implemented, provide your projected implementation date (month and year) and a short note identifying the outstanding item (e.g. hardware, prOCeduree, tra1n1ng, teCnnSCal SpeCiffCatSOnS). W- Mm~K f ~ Z~a~ple'Fe

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m s MULTI-PLANT ISSUE NUMBER ACTION NO. ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I.A. 1. 1. 1 SHIFT TECHNICAL ADVISOR - ON DUTY . ~ o C o ~ ~ ~

  • I.A.l. l. 2 SHIFT TECHNICAL ADVISOR - TECH SPECS C AI.A.1.1.3 F001 SHIFT TECHNICAL ADVISOR - TRAINED PER I,L CAT B......
  • I.A.1. 1. 4 SHIFT TECHNICAL ADVISOR - DESCRIBE LONG TERM PROGRAM.

I.A.1.2 SHIFT SUPERVISOR RESPONSIBILITIES.

I.A.1.3.1 F002 SHIFT MANNING LIMIT OVERTIMES ..

I.A. 1. 3. 2 F002 SHIFT MANNING - MIN SHIFT CREW.

I.A. 2. 1. 1 IMMEDIATE UPGRADING OF RO 8c SRO TRAINING AND QUAL. - SRO EXPER C ~ ~ ~ ~ ~

I.A.2.1.2 IMMEDIATE UPGRADING OF RO 8 SRO TRAINING AND QUAL. SRO'S BE RO'S lYR. C

~ ~ ~ ~ ~ ~ ~

I.A.2.1.3 IMMEDIATE UPGRADING OF RO 8( SRO TRAINING AND QUAL. - 3 MO. TRAINING.

I.A. 2. 1. 4 F003 IMMEDIATE UPGRADING OF RO 8( SRO TRAINING AND QUAL. - MODIFY TRAINING.

I.A. 2. 1. 5 IMMEDIATE UPGRADING OF RO 8c SRO TRAINING AND QUAL. - FACILITY CERTIF.

I.A.2.3 ADMINISTRATION OF TRAINING PROGRAMS I A.3.1.1

~ REVISE SCOPE 8c CRITERIA FOR LICENSING EXAMS - INCREASE SCOPE .....

I.A.3.1.2 REVISE SCOPE 8 CRITERIA FOR LICENSING EXAMS - INCREASE PASSING GRADE I.A.3. 1. 3.A REVISE SCOPE & CRIT. FOR LIC. EXAMS - SIMULATOR PLANTS WITH SIMULATORS I.A.3.1.3. B REVISE SCOPE 8( CRIT. FOR LIC. EXAMS - SIMULATOR - OTHER PLANTS .+A...

  • I.B.1:2 EVALUATION OF ORGANIZATION & MANAGEMENT. C ~ ~ ~ ~

I.C.1.1 SHORT-TERN ACCIDENT & PROCEDURES REVIEW SB LOCA.

I.C. 1. 2. A '004 SHORT-TERM ACCID. 8( PROCEDURES REV. - INADEQ. CORE COOL. REANAL. GUIDELINES I. C. 1. 2. B F004 SHORT-TERM ACCID. 8( PROCEDURES REV. - INADEQ. CORE COOL. REVISE PROCEDURES I.C.1.3.A F005 SHORT-TERM ACCID. 8( PROCEDURES REV " TRANSIENTS 8c ACCDTS. REANAL GUIDELINES (PROC. GEN. PKG. )

I. C. 1. 3. B F005 SHORT-TERM ACCID. 8c PROCEDURES REV. - TRANSIENTS 8( ACCDRS. REVISE PROCEDURES (UPGRADED EOP'S)

I. C.2 SHIFT 8 RELIEF TURNOVER PROCEDURES I.C.3 I.C 4 SHIFT-SUPERVISOR RESPONSIBILITY . ~ ..................... ~ - ~ - .. ~ ~ - - -. ~ . ~ ~ - - ~ ~ - - - ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

C

~ CONTROL-ROOM ACCESS..

I.C.5 F006 FEEDBACK OF OPERATING EXPERIENCE..

I.C.6 F007 VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES

  • I.C.7.1 NSSS VENDOR REV. OF PROC - LOW POWER TEST PROGRAM.

"I.C.7;2 NSSS VENDOR REV. OF PROC - POWER ASCENSION 8( EMER. PROCS "I. C.B PILOT MON OF SELECTED EMERGENCY PROC FOR NTOLS I.D. 1 (See F008 8 F071) CONTROL-ROOM DESIGN REVIEWS (ENTER DATA FOR MPA F008 8c MPA F-071).

I.D.2.1 F009 PLANT-SAFETY-PARAMETER DISPLAY CONSOLE " DESCRIPTION. ~ 0 ~ ~ ~ ~ ~ ~ ~

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MULTI-PLANT ISSUE NUMBER ACTION NO. ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I. D.2.2 F009 PLANT-SAFETY PARAMETER DISPLAY CONSOLE - INSTALLED.

I.D.2.3 F009 "

PLANT-SAFETY PARAMETER DISPLAY CONSOLE - FULLY IMPLEMENTED.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Rh . Awol.

  • I.G. l. 1 TRAINING DURING LOW-POWER TESTING - PROPOSE TESTS "I.G.1.2 TRAINING DURING LOW-POWER TESTING SUBMIT ANAL. & PROCS
  • I.G. 1. 3 TRAINING DURING LOW-POWER TESTING - TRAINING & RESULTS II. B. 1. 1 REACTOR-COOLANT SYSTEM VENTS " DESIGN VENTS II. B. 1. 2 F010 REACTOR-COOLANT SYSTEM VENTS - INSTALL VENTS (LL CAT B).

II B. 1. 3

~ F010 REACTOR-COOLANT SYSTEM VENTS - PROCEDURES II. B.2. 1 PLANT SHIELDING - REVIEW DESIGNS

  • II.B. 2. 2 PLANT SHIELDING - CORRECTIVE ACTIONS TO ASSURE ACCESS
  • II B.2. 3

~ F011 PLANT SHIELDING - PLANT HODIFICATIONS (LL CAT B).

  • II.B.2. 4 PLANT SHIELDING - EQUIPMENT QUALIFICATION- NOT TRACKED AS A THI ACTION ITEM. ~ ~

C~ ~ ~ ~ ~ ~

"II. B. 3. 1 PQSTACCIDENT SAMPLING INTERIH SYSTEM. C

~ ~ ~ ~ ~

  • II.B. 3. 2 POSTACCIDENT SAMPLING " CORRECTIVE ACTIONS "II.B. 3. 3 POSTACCIOENT SAMPLING - PROCEDURES ~ ~

PQSTACCIDENT SAMPLING - PLANT MODIFICATIONS (LL CAT B).

A I I.B.3. 4 F012 ~ ~

t ~ ~ ~

II.B.4. 1 F013 TRAINING FOR MITIGATING CORE DAMAGE - DEVELOP TRAINING PROGRAM.

%II. B.4.2.A F013 TRAINING FOR MITIGATING CORE DAMAGE INITIAL.. C ~ ~ ~ ~ ~ ~ ~

  • II. B.4.2. B F013 TRAINING FOR MITIGATING CORE DAMAGE - COHPLETE.............

II.D. l. 1 RELIEF & SAFETY VALVE TEST REQUIREMENTS - SUBMIT PROGRAM..... ~ ~ ~ ~ ~ ~ ~ ~

  • II. D. l. 2. A RELIEF & SAFETY VALVE TEST RE(UIREHENTS - COMPLETE TESTING. C
  • II.D. 1.2. B F014 RELIEF & SAFETY VALVE TEST REQUIREMENTS - PLANT SPECIFIC REPORT C Aj/,fe2 II.D. 1. 3 RELIEF & SAFETY VAVLE TEST REQUIREHENTS'- BLOCK-VALVE TESTING. ~ ~ ~ ~ ~ ~ ~
  • II.D.3. 1 VALVE POSITION INDICATION INSTALL DIRECT INDICATIONS OF VALVE POS
  • II.0.3. 2 VALVE POSTION INDICATION - TECH SPECS ~ ~ ~ ~ ~ ~ ~
  • II. E. 1. 1. 1 F015 AFS EVALUATION-ANALYSIS (SEE NOTE 1)
  • II. E. 1. 1. 2 F015 AFS EVALUATION-SHORT TERM NODS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

(SEE NOTE 2)

II. E. 1.1. 3 F015 AFS -LONG TERN MODS (SEE NOTE 3) 2-

MULTI-PLANT ISSUE NUMBER ACTION NO. ISSUE TITLE LICENSEE IMPLEMENTATION STATUS II.E.1.2.1.A AFS INITIATION 8( FLOW-CONTROL GRADE I I. E. 1. 2. 1. B F016 AFS INITIATION 8( FLOW - SAFETY GRADE (

II.E.1.2.2.A AFS INITIATION 4 FLOW - FLOW INDICATION CONTROL GRADE

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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~ ~ ~ ~

"II.E.l.2.2.B AFS INITIATION 8( FLOW - LL CAT A TECH SPECS

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  • II.E.1.2.2.C F017 AFS INITIATION 8c FLOW - SAFETY GRADE

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C

  • II.E. 3. l. 1 EMERGENCY POWER FOR PRESSURIZER HEATERS - UPGRADE POWER SUPPLY

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C

  • II.E. 3 1. 2

~ EMERGENCY POWER FOR PRESSURIZER HEATERS - TECH SPECS

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II. E.4.1.1 DEDICATED HYDROGEN PENETRATIONS - DESIGN. nrA

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I I. E.4.2. 1-4 CONTAINMENT ISOLATION DEPENDABILITY - IMP. DIVERSE ISOLATION C.

  • II. E. 4 2.5. A

~ CONTAINMENT ISOLAT. DEPENDABILITY - CNTMT PRESS. SETPT. SEECIFIY PRESS

  • II.E.4.2. 5. B CONTAINMENT ISOLATION DEPENDABILITY - CNTMT PRESSURE SETPT. MOOS II. E.4.2.6 F019 CONTAINMENT ISOLATION DEPENDABILITY - CNTMT PURGE VALVES I I. E.4. 2. 7 F019 CONTAINMENT ISOLATION DEPENDABILITY - RADIATION SIGNAL ON PURGE VALVES
  • II.E.4.2.8 CONTAINMENT ISOLATION DEPENDABLITY - TECH SPECS
  • II.F. l. 1 F020 ACCIDENT MONITORING - PROCEDURES.
  • II. F. l. 2. A F020 ACCIDE)T - MONITORING - NOBLE GAS MONITOR.....

~ ~ ~ ~ ~

C

~ ~ ~

"II.F.1.2.B F021 ACCIDENT MONITORING - IODINE/PARTICULATE SAMPLING ......... - . - . - .. - - - . - . --

  • II.F.1.2. C F022 ACCIDENT MONITORING - CONTAINMENT HIGH-RANGE MONITOR.
  • II. F. 1. 2. D F023 ACCIDENT MONITORING - CONTAINMENT PRESSURE . (
  • II. F. l. 2. E F024 ACCIDENT MONITORING - CONTAINMENT WATER LEVEL

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~ ~

~

~ ~ ~ ~ ~ ~ ~

~ ~ ~

ACCIDENT MONITORING - CONTAINMENT HYDROGEN.

~

%II. F.1.2. F F025

  • II.F.2.1 INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE COOLING - PROCEDURES

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

C

~ ~ ~ ~ ~ ~ ~ ~

  • II.F.2. 2 INSTRUMENTATION FOR DETECT. OF INADE(UATE CORE COOLING - SUBCOOL METER-
  • II. F. 2. 3 F026 INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE COOLING - DESC. OTHER

~ ~

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~ ~ ~ ~ ~ ~ ~

  • II.F.2.4 F026 INSTRUMENTATION FOR DETECT. OF INADEQUATE CORE CLING INSTLL ADD'L INSTRUMENTATION.
  • II.G. 1. 1 POWER SUPP- FOR PRESSURIZER RELIEF, BLOCK VALVES 8( LEVEL IND. - UPGRADE

%I I.G. 1. 2 POWER SUPP. FOR PRESSURIZER RELIEF, BLOCK VALVES 8( LEVEL IND. TECH SP II. K. 1 (Oper. Reactors Only) IE BULLETINS 05, 79-06, 79-08.

I 4 MULTI-PLANT ISSUE NUMBER ACTION NO. ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

  • II. K. 1. 5 IE BULLETINS - REVIEM ESF VALVES "II. K. 1. 10 IE BULLETINS - OPERABILITY STATUS
  • II. K. l. 22 IE BULLETINS AUX. HEAT REM SYSTEM, PROC.

AI I. K. 1. 23 IE BULLETINS - RV LEVEL, PROCEDURES

  • II.K.2. 2 ORDERS ON 88IM PLANTS PROCEDURES TO CONTROL AFW IND OF ICS AII. K.2. & ORDERS ON 88W PLANTS UPGRADE AFM SYSTEM.

II.K.2.9 F027 ORDERS ON-8&M PLANTS FEMA ON ICS II.K.2. 10 F02& ORDERS ON 8&W PLANTS - SAFETY-GRADE TRIP "II. K. 2. 11 F029 ORDERS ON 88W PLANTS - OPERATOR TRAINING.

I I. K.2. 13 F030 ORDERS ON 88W PLANTS - THERMAL MECHANICAL REPORT (CE & W PLANTS ALSO).

I I. K.2. 14 F031 ORDERS ON 88M PLANTS LIFT FREQUENCY OF PORV'S 8 SV's II. K. 2 15

~ ORDERS ON B&W PLANTS - EFFECTS OF SLUG FLOW.

I I.K.2. 16 F032 ORDERS ON 8&W PLANTS - RCP SEAL DAMAGE I I. K.2. 17 F033 ORDERS ON 8&M PLANTS - YOIDING IN RCS (CE & M PLANTS ALSO).

II. K.2. 19 BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO 'ONCE THROUGH STM GENERATOR. ~A AI I. K.2. 20 F035 ORDERS ON 88W PLANTS SYSTEM RESPONSE TO SB LOCA.

+II. K.3. 1. A F036 88IO TASK FORCE - AUTOMATIC PORV ISOLATION DESIGN. ~

AIC

~ ~ ~ ~

"II. K. 3. 1. 8 FINAL RECOMMENDATIONS, 880 TASK FORCE - AUTO PORV ISO TEST/INSTALL h~

II. K.3.2 F037 B&0 TASK FORCE - REPORT ON PORV FAILURES C...

II. K.3.3 F03& 880 TASK FORCE REPORTING SY 8 RY FAILURES AND CHALLENGES C II.K.3.5.A F039 88IO TASK FORCE - AUTO TRIP OF RCP'S PROPOSED MODIFICATIONS II.K.3.5.8 F039 880 TASK FORCE - AUTO TRIP OF RCP'S MODIFICATIONS.

II.K.3.7 B&0 TASK FORCE EVALUATION OF PORY OPENING PROBABILITIES II.K.3.9 , F040 880 TASK FORCE - PID CONTROLLER MODIFICATION.

II.K.3.10 F041 880 TASK FORCE - PROPOSED ANTICIPATORY TRIP MODIFICATIONS II K.3. 11

~ 880 TASK FORCE - JUSTIFY USE OF CERTAIN PORY.

I I. K. 3. 12. A 880 TASK FORCE ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED MOOS I I. K. 3:12. 8 F042 880 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP INSTALL MODS............

II. K.3.13.A F043 B&0 TASK FORCE - HPCI 8 RCIC SYSTEM INITIATION LEVELS ANALYSIS.. NA I I. K. 3. 13. 8 F043 880 TASK FORCE - HPCI & RCIC INITIATION LEVELS MODIFICATION. A

4 P

MULTI-PLANT ISSUE NUMBER ACTION N0. ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

  • II. K.3. 14 F044 B80 TASK FORCE - ISO CONDENSER ISOLATION ON HIGH RAD..

II. K. 3. 15 F045 B80 TASK FORCE MODIFY HPCI & RCIC BRK DETECTION CIRCUITRY..

~ N8i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ c~

I I. K. 3. 16A F046 B80 TASK FORCE CHALLENGE & FAILURE OF RELIEF VALVES STUDY.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~, ~ ~

I I. K. 3. 16. B F046 B80 TASK FORCE - CHALLENGE & FAILURE OF RELIEF VALVES MODIFICATIONS. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

II. K. 3. 17 F047 B80 TASK FORCE - ECC SYSTEM OUTAGES C II.K.3.18.A F048 B80 TASK FORCE - ADS ACTUATION STUDY. hi/.

II. K.3.18.B F048 B80 TASK FORCE - ADS ACTUATION PROPOSED MODIFICATIONS nrp II.K.3.18.C F048 B80 TASK FORCE - ADS ACTUATION MODIFICATIONS ~

NA ~ ~

AI I. K.3. 19 F049 B80 TASK FORCE - INTERLOCK RECIRCULATORY PUMP MODIFICATIONS

  • II. K. 3. 20 B80 TASK FORCE - LOSS OF SVC WATER AT BRP jv~

I I. K. 3. 21. A F050 B&0 TASK FORCE RESTART OF CSS 8E LPCI LOGIC DESIGN. big I I. K. 3. 21. B F050 B80 TASK FORCE RESTART OF CSS & LPCI LOGIC DESIGN MODIFICATIONS ~ i~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

II. K.3.22.A F051 B80 TASK FORCE - RCIC SUCTION VERIFICATION PROCEDURES I I. K. 3. 22. B F051 B80 TASK FORCE " RCIC SUCTION MODIFICATION. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

I I. K.3. 24 F052 B80, TASK FORCE SPACE COOLING FOR HPCI/RCI LOSS OF AC POWER. /YA II. K.3. 25. A B80 TASK FORCE - POWER ON PUMP SEALS PROPOSED MODIFICATIONS A'C, II. K. 3. 25. B F053 B80 TASK FORCE - POWER ON PUMP SEALS MODIFICATIONS IV@

II. K.3.27 F054 B80 TRASK FORCE - COMMON REFERENCE LEVEL FOR BWRS h/A I I. K.3. 28 '055 B80 TASK FQRCE - QUALIFICATION OF ADS ACCUMULATORS .+if.

  • II. K.3. 29 F056 B80 TASK FORCE - PERFORMANCE OF ISOLATION CONDENSERS kg II. K.3. 30. A B80 TASK FORCE - SCHEDULE FOR OUTLINE OF SB LOCA MODEL C I I.K. 3. 30. B F057 B&0 TASK FORCE - SB LOCA MODEL, JUSTIFICATION. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

II. K.3. 30. C B&0 TASK FORCE - SB LOCA METHODS NEW ANALYSES C II. K.3. 31 F058 B80 TASK FORCE - COMPLIANCE WITH CFR 50.46... .C..

"II.K.3.40 880 TASK FORCE - RCP SEAL DAMAGE - COVERED BY II. K. 2.16 AND II. K. 3.25. hfP

%II.K.3.43 B&0 TASK FORCE - EFFECTS OF SLUG FLOW - COVERED BY II.K.2 15 nrA I I. K.3. 44 F059 B80 TASK FORCE - EVALUATE TRANSIENT WITH SINGLE FAILURE .

I I. K.3.45 F060 B80 TASK FORCE - ANALYSES TO SUPPORT. uA II. K.3.46 F061 RESPONSE TO LIST OF CONCERNS FROM ACRS CONSULTANT.

AII. K.,3. 57 F062 IDENTIFY WATER SOURCES PRIOR TO MANUAL ACTIVATION OF ADS +1

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I I I.A.1. 1 EMERGENCY PREPAREDNESS, SHORT TERM.

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MULTI-PLANT ISSUE NUMBER ACTION NO. ISSUE TITLE LICENSEE IMPLEMENTATION STATUS III.A.1.2. 1 UPGRADE EMERGENCY SUPPORT FACILITIES INTERIM TSC OSC 8 EOF C.

C I I I A.1.2. 2

~ UPGRADE EMERGENCY SUPPORT FACILITIES-DESIGN-INCORP. INTO F063/F064/F065. ~ ~ ~ ~ ~ ~ ~ ~ ~

(SEE F063, F064, F065)

I II.A.1. 2. 3 UPGRADE EHER SUPPORT FACILITIES - HODS INCORPOR. INTO F063, F064 8c F065.

(SEE F063, F064, F065)

II I.A. 2. 1 F067 UPGRADE PREPAREDNESS - UPGRADE EMERGENCY PLANS TO APP. E. 10 CFR 50.

I I I.A.2. 2 F068 UPGRADE PREPAREDNESS - METEOROLOGICAL DATA. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

"I I I. D. l. l. 1 PRIMARY COOLANT OUTSIDE CONTAINMENT - LEAK REDUCTION . C~ ~ ~ ~ ~ ~ ~ ~

  • I D.

II. l. l. 2 PRIMARY COOLANT OUTSIDE CONTAINMENT - TECH SPECS ~ ~ ~ ~ ~ ~

C II I.D. 3.3. 1 INPLANT RAD. MONIT. PROVIDE MEANS TO DETER. PRESENCE OF RADIOIODINE I I I.D.3.3. 2 F069 INPLANT RADIATION MONIT. - HODIFICATIONS TO ACCURATELY MEAS. IODINE C ~ ~ ~ ~ ~ ~

II I. D.3.4. 1 F070 -

CONTROL ROOM HABITABILITY REVIEW. ~ ~ ~ ~ ~ ~ ~

  • I I I. D.3.4. 2 F070 -

CONTROL ROOM HABITABILITY SCHEDULE MODIFICATIONS

  • I I I.D. 3.4. 3 -

CONTROL ROOM HABITABILITY IMPLEMENT MODIFICATIONS HPA-F008 F008 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN.

HPA-F063 'F063 III.A,1.2 TECHNICAL SUPPORT CENTER.

MPA"F064 F064 III.A. 1.2 OPERATIONAL SUPPORT CENTER..............................-. ~ ...

HPA-F065 F065 II I ~ A..l. 2 EMERGENCY OPERATIONS FACILITY HPA-F071 'F071 I.D.1.2 DETAILED CONTROL ROOM REVIEW (FOLLOWUP TO F-8) ~ ~ ~ ~ ~ ~ ~

HPA-B072 MPA-B083 B072 B083 NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 8( 83-02).

TECH SPEC COVERED BY GENERIC LETTERS 83-26 8( 83-37 FOR NUREG-0737.

~ ~ \ Qi ~ ~ ~ ~ ~ ~

67.4.1 G001 REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12) ~ Q ~ ~

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